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Abstract <p>The impact of the concentration of the initial nitric acid actinide solutions on the thermochemical denitration in a thin-film rotary apparatus, on the entrainment of actinides into a local gas purification system, and on the physicochemical and some technological characteristics of the obtained uranyl(VI)–thorium formate powders (with thorium taken as a plutonium simulator) was determined. At the initial U + Th concentration in the solution of 200 g/L, the productivity was 65.20 g/h, the bulk density with/without tapping was 841 ± 45/704 ± 31 g/dm<sup>3</sup>, and the specific surface area was 0.69 ± 0.07 m<sup>2</sup>/g. The particle shape is predominantly spheroidal, which, in our opinion, will favor good fluidity of the powder during the reduction in a rotary tube furnace installed in the existing production facility for producing a pilot batch of uranium–plutonium oxide fuel.</p>

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The Impact of Uranium–Thorium Nitric Acid Solution Concentration on the Properties of Powders Produced by Thermochemical Denitration

  • 期刊论文

  • 发表日期：

    2025年10月1日

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  • A. S. Aloy,
  • K. Yu. Vergazov,
  • R. A. Serebryanskikh,
  • P. V. Slastikhin,
  • A. A. Khorshev

摘要

Abstract

The impact of the concentration of the initial nitric acid actinide solutions on the thermochemical denitration in a thin-film rotary apparatus, on the entrainment of actinides into a local gas purification system, and on the physicochemical and some technological characteristics of the obtained uranyl(VI)–thorium formate powders (with thorium taken as a plutonium simulator) was determined. At the initial U + Th concentration in the solution of 200 g/L, the productivity was 65.20 g/h, the bulk density with/without tapping was 841 ± 45/704 ± 31 g/dm3, and the specific surface area was 0.69 ± 0.07 m2/g. The particle shape is predominantly spheroidal, which, in our opinion, will favor good fluidity of the powder during the reduction in a rotary tube furnace installed in the existing production facility for producing a pilot batch of uranium–plutonium oxide fuel.